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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20210L1501999-08-0404 August 1999 Application for Amends to Licenses NPF-4 & NPF-7,ack Establishment of Seal Injection for RCP in Isolated & Drained Loop as Prerequisite for vacuum-assisted Backfill Technique & Extending Drained Loop Verification Time ML20206N3601999-05-0606 May 1999 Application for Amends to Licenses NPF-4 & NPF-7,revising Surveillance Frequency for RTS & ESFAS Analog Instrumentation Channels & Modifying AOT & Action Times for RTS & ESFAS Analog Instrumentation Channels ML20206G8271999-05-0303 May 1999 Application for Amends to Licenses NPF-4 & NPF-7,deleting &/Or Relocating Addl primary-to-secondary Leak Rate Limits & Enhanced Leakage Monitoring Requirements Imposed Following 1987 SG Tube Rupture Event ML20206G8641999-05-0303 May 1999 Application for Amends to Licenses NPF-4 & NPF-7,increasing Allowable Leakage from ECCS Components,Establishing Consistent Licensing Basis for Accidents Requiring Dose Analysis & Clarifying Requirements of CREVS ML20195J4351998-11-18018 November 1998 Application for Amends to Licenses NPF-4 & NPF-7,revising Allowable Groundwater Elevations & Removal of Piezometer Device Numbers Associated with Svc Water Reservoir ML20195C9291998-11-10010 November 1998 Application for Amends to Licenses NPF-4 & NPF-7,revising TSs to Clarify Operability Requirements for Pressurizer Heaters & Emergency Power Source for Pressurizer Heaters ML20236U8571998-07-28028 July 1998 Application for Amend to Licenses NPF-04 & NPF-07,revising TS 3/4.1.2 Re RWST & Boron Concentration Ph Range Bases Change ML20236U8611998-07-28028 July 1998 Application for Amend to Licenses NPF-4 & NPF-7,revising EDG Section to Be Consistent W/Station Procedures Associated W/ Steady State Conditions & W Nuclear Safety Advisory Ltr,Nsal 93-022 ML20236U8261998-07-28028 July 1998 Application for Amends to Licenses NPF-4 & NPF-7,revising Testing Acceptance Criteria to Demonstrate Operability of Casing Cooling & Outside Recirculation Spray Pumps ML18153A2891998-03-25025 March 1998 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7,revising Station Mgt Titles to Reflect New Positions Approved by Vepc Power Board of Directors on 980220 ML20217E8931998-03-25025 March 1998 Application for Amends to Licenses NPF-4 & NPF-7,modifying Insp Frequency of EDGs & Establishing Configuration Risk Mgt Program to Support Risk Informed Tech Specs ML20202C5621998-02-0303 February 1998 Application for Amends to Licenses NPF-4 & NPF-7,modifying Insp Requirements & Frequency for RCP Flywheels & Eliminating Insp Requirements for Unit 1,reactor Coolant Flow Straighteners ML20202C3281998-02-0303 February 1998 Application for Amends to Licenses NPF-4 & NPF-7,modifying Testing Requirements for Reactor Trip Bypass Breaker ML20199H3661997-11-18018 November 1997 Application for Amends to Licenses NPF-4 & NPF-7,permitting Quarterly Testing of Turbine Governor & Throttle Valves. Non-proprietary Tr,Rev 1 to WCAP-14733 & Proprietary Tr,Rev 1 to WCAP-14732,encl.Proprietary Rept Withheld ML20199A1411997-11-0505 November 1997 Application for Amends to Licenses NPF-4 & NPF-7, Respectively.Amends Will Provide Administrative Controls in TS 3/4.9.7,to Permit Spent Fuel Pit Gate Movement Over Irradiated Fuel ML20141F3691997-05-14014 May 1997 Application for Amends to Licenses NPF-4 & NPF-7,revising Wording in Surveillance Requirement 4.7.1.7.2.a to Clarify Testing & Insp Methodology of Turbine Governor Control Valves.Clarification Also Provided in TS 3/4.7.1.7 ML20132E6091996-12-17017 December 1996 Application for Amends to Licenses NPF-4 & NPF-7,requesting Temporary Changes to Service Water Sys Piping Repair and Refurbishment ML18153A6331996-11-26026 November 1996 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7,respectively,eliminating Records Retention Requirements Section of Ts,Per GL 95-06 & Adminstrative Ltr 95-06 ML20134H0001996-11-0606 November 1996 Application for Amends to Licenses NPF-4 & NPF-7,modifying Requirements for Isolated Loop Startup to Permit Filling of Drained Isolated Loop Via Backfill from RCS Through Partially Opened Loop Stop Valves ML20107L3881996-04-25025 April 1996 Application for Amends to Licenses NPF-4 & NPF-7,providing Suppl Info That Clarifies TS to Allow Switching of Charging & low-head SI Pumps During Unit Shutdown Conditions ML20101F7891996-03-21021 March 1996 Application for Amends to Licenses NPF-4 & NPF-7,clarifying Requirements for Testing Charcoal Adsorbent in Waste Gas Charcoal Filter Sys,Cr Emergency Habitability Sys & Safeguard Area Ventilation Sys ML20097C0001996-01-31031 January 1996 Application for Amends to Licenses NPF-4 & NPF-7, Respectively,Revising Current Minimum EDG Fuel Oil Day Tank Vol & Allowing Credit to Be Taken for Surveillance Testing Performed During Power to Satisfy SR Required in Shutdown ML20097J4281996-01-30030 January 1996 Application for Amends to Licenses NPF-4 & NPF-7, Respectively,Modifying Table 3.2.-1 TS 3.2.5 to Increase Minimum Allowable RCS Total Flow Rate from 284,000 Gpm & 275,000 Gpm to 295,000 Gpm ML20096G9811996-01-23023 January 1996 Application for Amends to Licenses NPF-4 & NPF-7,permitting Use of 10CFR50 App J,Option B,performance-based Containment Lrt ML20094N7881995-11-20020 November 1995 Application for Amends to Licenses NPF-4 & NPF-7,permitting Use of 10CFR50 App J,Option B,performance-based Containment Leakage Rate Testing ML20094D0131995-10-25025 October 1995 Application for Amends to Licenses NPF-4 & NPF-7,re Allowed Outage Time for PORV Nitrogen Accumulators & Separate Actions for PORV Inoperability ML20093K5851995-10-17017 October 1995 Application for Amend to License NPF-7,modifying Table 4.4-1 of TS 4.4.5.1 to Reduce from Two to One Min Number of SGs Required to Be Inspected During First ISI Following SG Replacement ML20093K6011995-10-17017 October 1995 Application for Amends to Licenses NPF-4 & NPF-7,modifying TS to Allow Both Containment Personnel Airlock Doors to Remain Open During Refueling Operations ML20092J4171995-09-19019 September 1995 Application for Amends to Licenses NPF-4 & NPF-7,increasing Surveillance Test Interval & Extending Visual & Surface Insps for Turbine Reheat Stop & Intercept Valves ML20092J2951995-09-19019 September 1995 Application for Amends to Licenses NPF-4 & NPF-7,revising Maximum Allowable Power Range Neutron Flux High Setpoints for Operation W/Inoperable MSSV ML20092A2421995-09-0101 September 1995 Application for Amends to Licenses NPF-4 & NPF-7,allowing Single Outage of Up to 14 Days for Each EDG Once Every 18 Months ML20087G3421995-03-30030 March 1995 Application for Amends to Licenses NPF-4 & NPF-7, Re Two Svc Water Loops to Be Isolated from Component Cooling Water Heat Exchangers During Power Operation in Order to Refurbish Isolated Svc Water Headers ML20080Q5421995-03-0202 March 1995 Application for Amends to Licenses NPF-4 & NPF-7,changing TS Associated W/Type a Testing Requirements Specified in App J to 10CFR50 ML20080B6801994-11-29029 November 1994 Application for Amends to Licenses NPF-4 & NPF-7,updating Environ Protection Plans to Reflect Current Obligations to Commonwealth of VA & Revise Portions of Transmission Corridor rights-of-way Erosion Control Program ML20076L5751994-10-25025 October 1994 Application for Amends to Licenses NPF-4 & NPF-7,extending Functional Surveillance Testing Frequency for Hydrogen Recombiners from Once Per 6 Months to Once Per 18 Months ML20069P3851994-06-16016 June 1994 Application for Amends to Licenses NPF-4 & NPF-7,revising TS Re Removal of Unnecessary EDG Surveillance Requirements,Per GL 93-05 ML20069K2371994-06-0909 June 1994 Application for Amends to Licenses NPF-4 & NPF-7,relocating TS Tables of Response Time Limits for RTS & ESFAS from TS to Station Controlled Documents,Per GL 93-08 ML20065K0981994-04-15015 April 1994 Application for Amends to Licenses NPF-4 & NPF-7,modifying P/T Operating Limitations During Heatup & Cooldown & LTOP Sys Pressure Setpoints & Enabling Temps for Units 1 & 2. Nonproprietary Westinghouse Rept WCAP-13831,Rev 1 Encl ML20065E1531994-03-30030 March 1994 Application for Amends to NPF-4 & NPF-7,revising High Head Safety Injection Flow Balance Surveillance Requirements by Removing Specific Numerical Values & Replacing W/Broader Requirement to Ensure HHSI Rate Meet LOCA Criteria ML20064F9681994-03-0909 March 1994 Correction to 930716 Proposed TS Change,Modifying TS to Conform W/Recent Changes to 10CFR20,correcting Administrative Error on TS Bases Page B 3/4 7-7 for Unit 2 as Issued by Amend 159 to License NPF-7 on 940217 ML20064C1531994-03-0101 March 1994 Application for Amends to Licenses NPF-4 & NPF-7,eliminating Unnecessary EDG Surveillance Requirements in Accordance W/Gl 93-05 & NUREG-1366 ML18153A8801994-02-25025 February 1994 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7,modifying Surveillance Frequency of Nozzles in Containment & Recirculation Spray Sys in Accordance W/Gl 93-05, Line-Item TS Improvements to Reduced Srs.... ML18153B4301993-12-27027 December 1993 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7,changing TS to Revise Review Responsibilities of Station Nuclear Safety & Operating Committee & Mgt Safety Review Committee ML20058M0581993-12-10010 December 1993 Application for Amends to Licenses NPF-4 & NPF-7,modifying Surveillance Frequency of Auxiliary Feedwater Sys Pumps from Monthly to Quarterly Per Generic Ltr 93-05 ML20058C4491993-11-19019 November 1993 Application for Amend to Licenses NPF-4 & NPF-7,allowing Use of Solid Rods or Zirconium Alloy or Stainless Steel Filler Rods to Replace Fuel Rods Which Have Been Identified as Failed & Deleting Individual Fuel Rod U Weight Limit ML20059K1271993-11-10010 November 1993 Application for Amends to Licenses NPF-4 & NPF-7,eliminating Simulated Reactor Coolant Pump Seal Injection Flow Requirement for Flow Balancing of High Head Safety Injection Lines ML18153D3951993-07-20020 July 1993 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7 Proposing Changes of Deletion of Requirement for Station Nuclear Safety & Operating Committee & Audit Frequencies ML18153D3931993-07-16016 July 1993 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7 to Implement Revised 10CFR20,revise Frequency of Radiological Effluent Release Repts from Semiannual to Annual & Clarify Site Maps ML20045G7591993-07-0808 July 1993 Application for Amends to Licenses NPF-4 & NPF-7, Respectively,Deleting Requirement to Periodically Review Certain Administrative & Technical Procedures ML20045G6831993-07-0202 July 1993 Application for Amends to Licenses NPF-4 & NPF-7 Modifying Table 4.4-1 of TS 4.4.5.1 to Reduce Minimum Number of SGs Required to Be Opened for Insp During First Insp (I.E.,Refueling Outage)Following SG Replacement 1999-08-04
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20210L1501999-08-0404 August 1999 Application for Amends to Licenses NPF-4 & NPF-7,ack Establishment of Seal Injection for RCP in Isolated & Drained Loop as Prerequisite for vacuum-assisted Backfill Technique & Extending Drained Loop Verification Time ML20206N3601999-05-0606 May 1999 Application for Amends to Licenses NPF-4 & NPF-7,revising Surveillance Frequency for RTS & ESFAS Analog Instrumentation Channels & Modifying AOT & Action Times for RTS & ESFAS Analog Instrumentation Channels ML20206G8271999-05-0303 May 1999 Application for Amends to Licenses NPF-4 & NPF-7,deleting &/Or Relocating Addl primary-to-secondary Leak Rate Limits & Enhanced Leakage Monitoring Requirements Imposed Following 1987 SG Tube Rupture Event ML20206G8641999-05-0303 May 1999 Application for Amends to Licenses NPF-4 & NPF-7,increasing Allowable Leakage from ECCS Components,Establishing Consistent Licensing Basis for Accidents Requiring Dose Analysis & Clarifying Requirements of CREVS ML20195J4351998-11-18018 November 1998 Application for Amends to Licenses NPF-4 & NPF-7,revising Allowable Groundwater Elevations & Removal of Piezometer Device Numbers Associated with Svc Water Reservoir ML20195C9291998-11-10010 November 1998 Application for Amends to Licenses NPF-4 & NPF-7,revising TSs to Clarify Operability Requirements for Pressurizer Heaters & Emergency Power Source for Pressurizer Heaters ML20236U8611998-07-28028 July 1998 Application for Amend to Licenses NPF-4 & NPF-7,revising EDG Section to Be Consistent W/Station Procedures Associated W/ Steady State Conditions & W Nuclear Safety Advisory Ltr,Nsal 93-022 ML20236U8571998-07-28028 July 1998 Application for Amend to Licenses NPF-04 & NPF-07,revising TS 3/4.1.2 Re RWST & Boron Concentration Ph Range Bases Change ML20236U8261998-07-28028 July 1998 Application for Amends to Licenses NPF-4 & NPF-7,revising Testing Acceptance Criteria to Demonstrate Operability of Casing Cooling & Outside Recirculation Spray Pumps ML20217E8931998-03-25025 March 1998 Application for Amends to Licenses NPF-4 & NPF-7,modifying Insp Frequency of EDGs & Establishing Configuration Risk Mgt Program to Support Risk Informed Tech Specs ML18153A2891998-03-25025 March 1998 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7,revising Station Mgt Titles to Reflect New Positions Approved by Vepc Power Board of Directors on 980220 ML20202C3281998-02-0303 February 1998 Application for Amends to Licenses NPF-4 & NPF-7,modifying Testing Requirements for Reactor Trip Bypass Breaker ML20202C5621998-02-0303 February 1998 Application for Amends to Licenses NPF-4 & NPF-7,modifying Insp Requirements & Frequency for RCP Flywheels & Eliminating Insp Requirements for Unit 1,reactor Coolant Flow Straighteners ML20199H3661997-11-18018 November 1997 Application for Amends to Licenses NPF-4 & NPF-7,permitting Quarterly Testing of Turbine Governor & Throttle Valves. Non-proprietary Tr,Rev 1 to WCAP-14733 & Proprietary Tr,Rev 1 to WCAP-14732,encl.Proprietary Rept Withheld ML20199A1411997-11-0505 November 1997 Application for Amends to Licenses NPF-4 & NPF-7, Respectively.Amends Will Provide Administrative Controls in TS 3/4.9.7,to Permit Spent Fuel Pit Gate Movement Over Irradiated Fuel ML20149F1201997-07-17017 July 1997 Amends 205 & 186 to Licenses NPF-4 & NPF-7,respectively, Addressing Proposed Temporary (Limit by Time Duration) TS Changes for Svc Water Sys Refurbishment ML20141F3691997-05-14014 May 1997 Application for Amends to Licenses NPF-4 & NPF-7,revising Wording in Surveillance Requirement 4.7.1.7.2.a to Clarify Testing & Insp Methodology of Turbine Governor Control Valves.Clarification Also Provided in TS 3/4.7.1.7 ML20132E6091996-12-17017 December 1996 Application for Amends to Licenses NPF-4 & NPF-7,requesting Temporary Changes to Service Water Sys Piping Repair and Refurbishment ML18153A6331996-11-26026 November 1996 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7,respectively,eliminating Records Retention Requirements Section of Ts,Per GL 95-06 & Adminstrative Ltr 95-06 ML20134H0001996-11-0606 November 1996 Application for Amends to Licenses NPF-4 & NPF-7,modifying Requirements for Isolated Loop Startup to Permit Filling of Drained Isolated Loop Via Backfill from RCS Through Partially Opened Loop Stop Valves ML20107L3881996-04-25025 April 1996 Application for Amends to Licenses NPF-4 & NPF-7,providing Suppl Info That Clarifies TS to Allow Switching of Charging & low-head SI Pumps During Unit Shutdown Conditions ML20101F7891996-03-21021 March 1996 Application for Amends to Licenses NPF-4 & NPF-7,clarifying Requirements for Testing Charcoal Adsorbent in Waste Gas Charcoal Filter Sys,Cr Emergency Habitability Sys & Safeguard Area Ventilation Sys ML20097C0001996-01-31031 January 1996 Application for Amends to Licenses NPF-4 & NPF-7, Respectively,Revising Current Minimum EDG Fuel Oil Day Tank Vol & Allowing Credit to Be Taken for Surveillance Testing Performed During Power to Satisfy SR Required in Shutdown ML20097J4281996-01-30030 January 1996 Application for Amends to Licenses NPF-4 & NPF-7, Respectively,Modifying Table 3.2.-1 TS 3.2.5 to Increase Minimum Allowable RCS Total Flow Rate from 284,000 Gpm & 275,000 Gpm to 295,000 Gpm ML20096G9811996-01-23023 January 1996 Application for Amends to Licenses NPF-4 & NPF-7,permitting Use of 10CFR50 App J,Option B,performance-based Containment Lrt ML20094N7881995-11-20020 November 1995 Application for Amends to Licenses NPF-4 & NPF-7,permitting Use of 10CFR50 App J,Option B,performance-based Containment Leakage Rate Testing ML20094D0131995-10-25025 October 1995 Application for Amends to Licenses NPF-4 & NPF-7,re Allowed Outage Time for PORV Nitrogen Accumulators & Separate Actions for PORV Inoperability ML20093K6011995-10-17017 October 1995 Application for Amends to Licenses NPF-4 & NPF-7,modifying TS to Allow Both Containment Personnel Airlock Doors to Remain Open During Refueling Operations ML20093K5851995-10-17017 October 1995 Application for Amend to License NPF-7,modifying Table 4.4-1 of TS 4.4.5.1 to Reduce from Two to One Min Number of SGs Required to Be Inspected During First ISI Following SG Replacement ML20092J4171995-09-19019 September 1995 Application for Amends to Licenses NPF-4 & NPF-7,increasing Surveillance Test Interval & Extending Visual & Surface Insps for Turbine Reheat Stop & Intercept Valves ML20092J2951995-09-19019 September 1995 Application for Amends to Licenses NPF-4 & NPF-7,revising Maximum Allowable Power Range Neutron Flux High Setpoints for Operation W/Inoperable MSSV ML20092A2421995-09-0101 September 1995 Application for Amends to Licenses NPF-4 & NPF-7,allowing Single Outage of Up to 14 Days for Each EDG Once Every 18 Months ML20087G3421995-03-30030 March 1995 Application for Amends to Licenses NPF-4 & NPF-7, Re Two Svc Water Loops to Be Isolated from Component Cooling Water Heat Exchangers During Power Operation in Order to Refurbish Isolated Svc Water Headers ML20080Q5421995-03-0202 March 1995 Application for Amends to Licenses NPF-4 & NPF-7,changing TS Associated W/Type a Testing Requirements Specified in App J to 10CFR50 ML20080B6801994-11-29029 November 1994 Application for Amends to Licenses NPF-4 & NPF-7,updating Environ Protection Plans to Reflect Current Obligations to Commonwealth of VA & Revise Portions of Transmission Corridor rights-of-way Erosion Control Program ML20076L5751994-10-25025 October 1994 Application for Amends to Licenses NPF-4 & NPF-7,extending Functional Surveillance Testing Frequency for Hydrogen Recombiners from Once Per 6 Months to Once Per 18 Months ML20069P3851994-06-16016 June 1994 Application for Amends to Licenses NPF-4 & NPF-7,revising TS Re Removal of Unnecessary EDG Surveillance Requirements,Per GL 93-05 ML20069K2371994-06-0909 June 1994 Application for Amends to Licenses NPF-4 & NPF-7,relocating TS Tables of Response Time Limits for RTS & ESFAS from TS to Station Controlled Documents,Per GL 93-08 ML20065K0981994-04-15015 April 1994 Application for Amends to Licenses NPF-4 & NPF-7,modifying P/T Operating Limitations During Heatup & Cooldown & LTOP Sys Pressure Setpoints & Enabling Temps for Units 1 & 2. Nonproprietary Westinghouse Rept WCAP-13831,Rev 1 Encl ML20065E1531994-03-30030 March 1994 Application for Amends to NPF-4 & NPF-7,revising High Head Safety Injection Flow Balance Surveillance Requirements by Removing Specific Numerical Values & Replacing W/Broader Requirement to Ensure HHSI Rate Meet LOCA Criteria ML20064F9681994-03-0909 March 1994 Correction to 930716 Proposed TS Change,Modifying TS to Conform W/Recent Changes to 10CFR20,correcting Administrative Error on TS Bases Page B 3/4 7-7 for Unit 2 as Issued by Amend 159 to License NPF-7 on 940217 ML20064C1531994-03-0101 March 1994 Application for Amends to Licenses NPF-4 & NPF-7,eliminating Unnecessary EDG Surveillance Requirements in Accordance W/Gl 93-05 & NUREG-1366 ML18153A8801994-02-25025 February 1994 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7,modifying Surveillance Frequency of Nozzles in Containment & Recirculation Spray Sys in Accordance W/Gl 93-05, Line-Item TS Improvements to Reduced Srs.... ML18153B4301993-12-27027 December 1993 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7,changing TS to Revise Review Responsibilities of Station Nuclear Safety & Operating Committee & Mgt Safety Review Committee ML20058M0581993-12-10010 December 1993 Application for Amends to Licenses NPF-4 & NPF-7,modifying Surveillance Frequency of Auxiliary Feedwater Sys Pumps from Monthly to Quarterly Per Generic Ltr 93-05 ML20058C4491993-11-19019 November 1993 Application for Amend to Licenses NPF-4 & NPF-7,allowing Use of Solid Rods or Zirconium Alloy or Stainless Steel Filler Rods to Replace Fuel Rods Which Have Been Identified as Failed & Deleting Individual Fuel Rod U Weight Limit ML20059K1271993-11-10010 November 1993 Application for Amends to Licenses NPF-4 & NPF-7,eliminating Simulated Reactor Coolant Pump Seal Injection Flow Requirement for Flow Balancing of High Head Safety Injection Lines ML18153D3951993-07-20020 July 1993 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7 Proposing Changes of Deletion of Requirement for Station Nuclear Safety & Operating Committee & Audit Frequencies ML18153D3931993-07-16016 July 1993 Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7 to Implement Revised 10CFR20,revise Frequency of Radiological Effluent Release Repts from Semiannual to Annual & Clarify Site Maps ML20045G7591993-07-0808 July 1993 Application for Amends to Licenses NPF-4 & NPF-7, Respectively,Deleting Requirement to Periodically Review Certain Administrative & Technical Procedures 1999-08-04
[Table view] |
Text
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.O ViluilNI A El.ECTRIC ANI> POwen CONWANY RICitMOND, VHMilNE A U261
, July 28, 1998 U.S. Nuclear Regulatory Commission Serial No.98-435 Attention: Document Control Desk NL&OS/GSS/ETS R0 Washington, D.C. 20555 Docket Nos. 50-338 50-339 i License Nos. NPF-4 !
NPF-7 !
Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATION CHANGE EDG STEADY STATE FREQUENCY REQUIREMENTS Pursuant to 10 CFR 50.90, Virginia Electric and Power Company requests amendments, in the form of changes to the Technical Specifications and to Facility Operating License Numbers NPF-4 and NPF-7 for North Anna Power Station Units 1 and 2, respectively. The proposed changes will revise the EDG section to be consistent with station procedures associated with steady state conditions and Westinghouse Nuclear Safety Advisory Letter, NSAL 93-022. A discussion of the proposed Technical Specifications changes is provided in Attachment 1.
The proposed Technical Specifications changes have been reviewed and approved by j the Station Nuclear Safety and Operating Committee and the Management Safety Review Committee. It has been determined that the proposed Technical Specifications .
/
changes do not involve an unreviewed safety question as defined in 10 CFR 50.59 or a significant hazards consideration as defined in 10 CFR 50.92. The proposed Technical l Specifications changes are provided as a mark-up in Attachment 2 and a typed version
! in Attachment 3. The basis for our determination that the changes do not involve a significant hazards consideration is provided in Attachment 4. [igyj y If you have any fudher questions, please contact us.
l Very truly yours, 1
James P. O'Hanlon Senior Vice President - Nuclear 9807310121 980728 PDR ADOCK 05000338 P PDR L
4
(
- 1. Discussion of Changes
- 2. Mark-up of Technical Specifications Changt '
l 3. Proposed Technical Specifications Changes j 4. Significant Hazards Consideration Determination l
l Commitments made in this letter:
i
- 1. There are no commitments in this letter i
cc: U.S. Nuclear Regulatory Commission l
Region ll Atlanta Federal Center 61 Forsyth Street, SW !
Suite 23T85 Atlanta, Georgia 30303 i
i Mr. M. J. Morgan l NRC Senior Resident inspector North Anna Power Station Commissioner Department of Radiological Health l Room 104A 1500 East Main Street Richmond, VA 23219 1
. 1 l
COMMONWEALTH OF VIRGINIA ) l
)
COUNTY OF HENRICO ) 1 The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by J. P. O'Hanlon, who is Senior Vice President - Nuclear, of Virginia Electric and Power Company. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of his knowledge and belief.
Ac (nowledged before me thisO day of f ,19h .
My Commission Expires: Marcil 31, 2000.
00bt (04bh
/ Notary Public l
e (SEAL)
L_____________
1 I
l 1
1 i
Attachment 1 l
Discussion of Change 1
l l
l l
1 l
l North Anna Power Station Units 1 and 2 Virginia Electric and Power Company i
1 Di curi:n cf Ch;nges i introduction l -
. Pursuant to 10 CFR 50.90, Virginia Electric and Power Company requests changes to
\
l Technical Specifications Surveillance Requirements 4.8.1.1.2.a.4, 4.8.1.1.2.c,
- 4.8.1,1.2.d.2, 4.8.1.1.2.d.4.b, 4.8.1.1.2.d.5, 4.8.1.1.2.d.6.b, 4.8.1.1.2.d.11.b, and l 4.8.1.1.2.e for North Anna Power Station Units 1 and 2. The Technical Specifications
! sunmillance requirements currently require each Emergency Diesel Generator (EDG) to be l
l demonstrated OPERABLE by the performance of the specific Surveillance Requirements.
One significant pa t of demonstrating operability of the EDG requires verification that the l frequency is within a specified range. This requirement is currently reflected in the North ;
Anna Technical Specifications as 60 i 1.2 Hz. Based upon a 1993 Westinghouse Nuclear l Safety Advisory Letter (NSAL 93-022), North Anna procedures were revised to reflect a 1 l
narrower EDG frequency range in 1995 of 60 i 0.5 Hz. The NSAL indicated that Westinghouse accident analyses assumed a steady state EDG frequency of 60 Hz, making no specific allowance for the effects on ESF pump performance at steady state frequency limits that are currently permitted by Technical Specifications.
Margin exists in the North Anna accident analyses to account for some level of frequency l variation from 60 Hz on the emergency bus supplied by the EDG, and i 0.5 Hz has been l evaluated by Engineering as acceptable.
l The proposed changes to the North Anna Units 1 and 2 Technical Specifications will not adversely affect the safe operation of the plant or result in an unreviewed safety question as defined by the criteria of 10 CFR 50.59.
Background
l Current Licensing Basis The original EDG testing requirements that verified the frequency were issued as part of amendment 83 dated August 28,1986 for North Anna Unit 1 and as part of the original operating licenses for Unit 2 dated August 21,1980. Unit 1 amendment 83 was part of the effort to make Unit 1 identical to the already approved Unit 2 Technical Specifications.
Page 1 of 7 l.
I
Currsnt De ign B: sis e
The EDG supplies the emergency bus with electrical power within 10 seconds of receiving ,
an emergency start signal. With the emergency bus de-energized, the EDG output breaker will'close when the EDG output voltage reaches 95% of rated voltage. The frequency requirement of 60 0.5 Hz is based on the analyzed steady state limit for the EDG. The EDG supplies the electrical power for the required equipment to mitigate the consequences of design basis events. The steady state voltage and frecuency limits of 4160 420 volts and 60 i 0.5 Hz ensure that the ESF pumps will supply the minimum flow necessary to maintain the fuel within the required PCT limits. ;
Safety Guide 9 is the primary licensing document for the North Anna Units and is considered the base document for licensing of the station. However, additional standards )
I and regulatory guides are used in part as references based on good engineering practice.
The guidance of IEEE308,1974, Section 4.3, Power Quality and Regulatory Guide 1.9, i Rev 1, Section C.5 (transient response to the disconnection of the largest single electrical load) were the technical reference sources considered in the evaluation for the frequency requirements for transient and staady state conditions and for making this change to the Technical Specification.
l Discussion
( During a review of the EDG System, Virginia Power's resolution of an issue involving EDG
- frequency range control stemming from a 1993 Westinghouse Nuclear Safety Advisory Letter (NSAL 93-022) was reviewed. The letter indicated that the Westinghouse accident analyses assumed a steady state EDG frequency of 60 HZ, making no specific allowance for the effects on ESF pump performance at steady state frequency limits that are currently permitted by Technical Specifications. The review determined that earlier engineering assessments were made which found that steady-state EDG operation at the limits permitted by the NAPS Technical Specifications could effect ECCS equipment ;
performance so that it would not support accident analysis assumed values. These assessments and reanalysis further determined an acceptable range of EDG frequency,60 ,
0.5 Hz, within which accident analysis assumptions would be met. This range was Page 2 of 7
incorporated into station procedures. Thsrefore, a TS change is needed to reestablish TS control of EDG frequency at these new values.
Specific Changes The following Technical Specification changes applies to both Units 1 and 2:
- 1. Surveillance Requirement 4.8.1.1.2.a.4 requires each EDG to be demonstrated OPERABLE by verification that the EDG can start and gradually accelerate to synchronous speed (900 rpm). The EDG must maintain a generator voltage of 4160 420 volts and a frequency of 60 1.2 Hz. The proposed change will limit the steady state frequency range to 60 0.5 Hz and will eliminate the reference to the synchronous speed of 900 rpm.
- 2. Surveillance Requirement 4.8.1.1.2.c requires at least once per 184 days that each EDG will be demonstrated OPERABLE by starting and accelerating to 900 rpm in s 10 seconds. The EDG voltage and frequency limits for this start are 4160 420 volts and 60 1.2 Hz. The EDG is then required to be synchronized to the emergency bus, gradually loaded to an indicated 2500 to 2600 kw, and operated for at least 60 minutes.
The proposed change modifies the 10 seconds start requirements to achieve voltage and frequency of 2 3960 volts and 2 59.5 Hz. It also removes the statement of obtaining 900 rpm. The voltage requirement is based on the EDG output breaker close permissive (95% voltage). Furthermore, it establishes a steady state voltage and frequency c,f 4160 i 420 volts and 60 i 0.5 Hz.
- 3. Surveillance Requirement 4.8.1.1.2.d.2 requires each EDG to be demonstrated OPERABLE at least once every 18 months during shutdown by verification that the EDG can reject a load of 610 kW. The EDG is required to snaintain a generator voltage of 4160 420 volts and a frequency of 60 1.2 Hz during the transient. The proposed change will limit the steady state frequency range following the transient to 60 0.5 Hz.
The upper frequency limit is 66 Hz during the transient based on the allowed value obtained from R.G.1.9, Rev.1, Section C.5 related to transient frequency response for Page 3 of 7
the di; conn::ction of tha larg:st single lord. Tha 3 cccond acceptanca critsria for recovery to steady state is based on 60% of a 5 second load block time per R.G.1.9, however, the use for a load rejection is not the same in terms of applying this criteria.
.' The criteria was, however, considered to be an acceptable conservative response time for governor speed recovery to the new more restrictive steady state frequency range of 60 i 0.5 Hz following the single largest load rejection test.
- 4. Surveillance Requirement 4.8.1.1.2.d.4.b requires each EDG t'o be demonstrated l
OPERABLE at least once every 18 months during shutdown by verification that the
! EDG can start on a simulated loss of offsite power. The EDG is required to start and energize the emergency buses with all. permanently connected loads within 10 seconds, energize the auto-connected shutdown loads through the sequencing times, and operate for 2 5 minutes. The EDG is required to maintain a generator steady state voltage of 4160 + 420 volts and steady state frequency of 60 1.2 Hz. The proposed change will limit the steady state frequency range to 60 i 0.5 Hz.
- 5. Surveillance Requirement 4.8.1.1.2.d.5 requires each EDG to be demonstrated OPERABLE at least once every 18 months during shutdown by verification that on an ESF actuation test signal the EDG starts on an auto start signal and operates for > 5 !
minutes. On the automatic start signal, the EDG voltage and frequency limits are 4160 420 volts and 60 1.2 Hz. The proposed change adds the 10 seconds start requirements for voltage and frequency. The voltage is required to be 2 3960 volts and the frequency is 2 59.5 Hz. The change also establishes steady state voltage and frequency of 4160 i 420 volts and 60 0.5 Hz.
- 6. Surveillance Requirement 4.8.1.1.2.d.6.b requires each EDG to be demonstrated OPERABLE at least once every 18 months during shutdown by verification that the EDG can start on a simulated loss of offsite power in conjunction with an ESF actuation test signal. The EDG is required to start and energize the emergency buses with all permanently connected loads within 10 seconds, energize the auto-connected shutdown loads through the sequencing time, and operate for 2 5 minutes. The EDG is also required to maintain a generator steady state voltage of 4160 420 volts and
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stsady etita frequ;ncy of 60 i 1.2 Hz. Th3 propos;d chango will limit the steady stato frequency range to 60 0.5 Hz.
l
' 7. Surveillance Requirement 4.8.1.1.2.d.11.b requires each EDG to be demonstrated l
OPERABLE at least once every 18 months during shutdown by verification that the EDG can restart after it has operated for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or until operating temperatures have
~
stabilized. The start and acceleration to at least 900 rpm is required within 10 seconds, and the voltage and frequency requirements are specified as 4160 420 volts and 60 l 1.2 Hz. The proposed change modifies the 10 seconds start requirements for voltage and frequency. The EDG is required to achieve a voltage 23960 volts and a frequency
, 2 59.5 Hz within 10 seconds and achieve a steady state vo'tage and frequency of 4160 i 420 volts and 60 i 0.5 Hz. The reference to the 900 rpm is being removed since it is synonymous to the frequency requirement.
- 8. Surveillance Requirement 4.8.1.1.2.e requires both EDGs to be demonstrated OPERABLE at least once every 10 years or after any modifications which could affect EDG interdependence by starting both EDGs simultaneously during shutdown. Each EDG is required to start and accelerate to at least 900 rpm within 10 seconds. The proposed change removes the 900 rpm requirement and replaces it with the criteria of achieving a voltage 2 3960 volts and a frequency 2 59.5 Hz within 10 seconds.
Safety Significance Virginia Electric and Power Company has reviewed the proposed Technical Specification changes against the requirements of 10 CFR 50.92 and has determined that the proposed changes would not pose a significant hazards consideration. Specifically, operation of the North Anna Power Station in accordance with the proposed Technical Specifications q j changes will not:
I t
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l 1. Involva c significant incrzse in tha probability or cons:qu:;nc:;s of cn cecident i
j previously evaluated.
l The proposed change provides a more stringent requirement for the EDG frequency i limit at steady state operation of 60 20.5 Hz from the current 6011.2 Hz. The change to the EDG frequency limit does not result in operation that will increase the !
l probability of initiating an analyzed event and does not alter assumptions relative to !
mitigation of an accident or transient event. The change to the frequency limit is l
acceptable because the safety analyses assumptions for emergency power limits the frequency variations to 6010.5 Hz and assumes that the EDG supplies the emergency bus with electrical power within 10 seconds of receiving an emergency start signal. The EDG output breaker will close with no electrical power applied to '
the emergency bus when the EDG output reaches 95% of rated voltage. The minimum frequency requirement of 59.5 Hz is based on the steady state limit for the EDG. The EDG supplies the electrical power for the required equipment to mitigate the consequences of design basis events. The minimum voltage and frequency (3740 volts and 59.5 Hz) limits ensure thst the ESF pumps will supply the minimum flow necessary to maintain the fuel within the required parameters to prevent degradation. Therefore, this change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed change provides a more stringent requirement for thr, EDG frequency at steady state operation of 6010.5 Hz from the current 6011.2 Hz. The change does not introduce a new mode of plant operation and does not involve physical modification to the plant. The proposed change does impose different requirements.
However, these changes are consistent with the assumptions in the safety analyses.
Thus, this change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
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- 3. Involva a significant reduction n a margin of safety.
The proposed change provides a more stringent requirement for the DG frequency at steady state operation of 6010.5 Hz from the current 6011.2 Hz. The change to I the frequency limit is acceptable because the safety analyses assumptions for emergency power limits the frequency variations to 6010.5_Hz and assumes that the EDG supplies the emergency bus with electrical power within 10 seconds of receiving an emergency start signal. The EDG output breaker will close with no electrical power applied to the emergency bus when the EDG output reaches 95%
of rated voltage. The minimum frequency requirement of 59.5 Hz is based on the steady state limit for the EDG. The EDG supplies the electrical power for the required equipment to mitigate the consequences of design basis events. The minimum voltage and frequency (3740 volts and 59.5 Hz) limits ensure that the ESF pumps will supply the minimum flow necessary to maintain the fuel within the required parameters and meet the accident analysis acceptance criteria. The margin of safety is established through the design of the plant structures, systems and components, the parameters within which the plant is operated, and the establishment of the setpoints for the actuation of equipment relied upon to respond to an event. The change, due to the short time period allowed in this condition, does not significantly impact the performance of structures; systems or components relied upon for accident mitigation or any safety analysis assumptions. Therefore, the change does not involve a significant reduction in a margin of safety.
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